A CANDU-SCWR With a Steam Generator: Preliminary Thermodynamic Assesment and Estimation of Fouling Rates.

摘要

The most commonly envisaged configuration of CANDU-SCWR (Super Critical Water Reactor) is a direct cycle which creates the potential for transport of radioactive corrosion products or fission products throughout the entire plant leading to activity fields in the turbines, condenser and feedwater train. A two-loop SCWR is proposed where a steam generator is used to contain the supercritical water coolant and generate steam in a conventional cycle.;To estimate the fouling rate on the tubes of the steam generator, a transport and deposition model was developed. Results indicate a deposition rate approximately 100 times higher than in conventional nuclear reactors. This results in a 4% decrease in efficiency over five years of operation.;The resulting decrease in efficiency and the optimum sizing of the steam generator were obtained from a general thermodynamic model of the plant. Parametric case studies indicate that two once-through IHXs of comparable size to conventional steam generators could be used to achieve an overall plant efficiency of 45%.